Curium Process Development. I. General Process Description

Abstract

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Steady-State Solvent Extraction Calculations for Curium Recovery

“…The program was used in the development of solvent extraction processes to recover curium produced by irradiating plutonium (Eubanks and Burney, 1966;Groh et al, 1965). 244Cm is potentially a good isotope for power sources because of its long half life, high specific power, and potential availability.…”

Calculation of Transient Behavior of Solvent Extraction Processes

“…The first example is from the Tramex process for the recovery of curium from irradiated plutonium (Eubanks and Burney, 1966;Groh et al, 1965). One step in the Tramex process separates curium from lanthanides by selectively extracting the curium into tertiary amine chlorides from a lithium chloride solution.…”

Separation of Milligram Quantities of 252Cf from Multigram Quantities of 244Cm and 243Am

“…The starting material was a solvent wash solution from a Tramex [11] cycle (solvent extraction with a mixture of tertiary amines) in the process for recovering 244 Cm from reactor-irradiated plutonium [12], The solution contained 0.4 M LiCl, 0.5 M HCl and significant quantities of 254 Es, 252 Cf, ^»Bk, 244 Cm, ^Arn, 154 Eu, and 144 Ce. After the solvent wash solution was concentrated, the actinides and lanthanides were precipitated by adding NH 4 OH.…”